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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Candidates for leadership provide statements: ANS Board of Directors
With the annual ANS election right around the corner, American Nuclear Society members will be going to the polls to vote for a vice president/president-elect, treasurer, and members-at-large for the Board of Directors. In January, Nuclear News published statements from candidates for vice president/president-elect and treasurer. This month, we are featuring statements from each nominee for the Board of Directors.
J. P. Nichols, R. E. Brooksbank, D. E. Ferguson
Nuclear Technology | Volume 1 | Number 2 | April 1965 | Pages 176-178
Technical Paper | doi.org/10.13182/NT65-A20487
Articles are hosted by Taylor and Francis Online.
Radiation levels and exposures associated with the operation of the ORNL Kilorod Facility for the fabrication of 233UO2-ThO2 fuel were determined and are analyzed. Comparison between the measured activity of 208 Tl during a typical sequence of operations and the calculated activity of pure 232 U demonstrates the effects of the several fabrication steps. Conceptual design calculations for a semi-continuously operating plant indicate that up to 100 kg/d of mixed oxide containing 200 parts/106 232 U can be processed using 2-in.-thick (5.1 cm) lead-equivalent shielding.